Accident tolerant fuel cladding development: Promise, status, and challenges
Abstract
The motivation for transitioning away from zirconium-based fuel cladding in light water reactors to significantly more oxidation-resistant materials, thereby enhancing safety margins during severe accidents, is laid out. A review of the development status for three accident tolerant fuel cladding technologies, namely coated zirconium-based cladding, ferritic alumina-forming alloy cladding, and silicon carbide fiber–reinforced silicon carbide matrix composite cladding, is offered. Technical challenges and data gaps for each of these cladding technologies are highlighted. Full development towards commercial deployment of these technologies is identified as a high priority for the nuclear industry.
- Authors:
-
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Org.:
- USDOE Office of Nuclear Energy (NE)
- OSTI Identifier:
- 1471930
- Alternate Identifier(s):
- OSTI ID: 1506714
- Grant/Contract Number:
- AC05-00OR22725
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of Nuclear Materials
- Additional Journal Information:
- Journal Volume: 501; Journal Issue: C; Journal ID: ISSN 0022-3115
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE
Citation Formats
Terrani, Kurt A. Accident tolerant fuel cladding development: Promise, status, and challenges. United States: N. p., 2018.
Web. doi:10.1016/j.jnucmat.2017.12.043.
Terrani, Kurt A. Accident tolerant fuel cladding development: Promise, status, and challenges. United States. https://doi.org/10.1016/j.jnucmat.2017.12.043
Terrani, Kurt A. Sat .
"Accident tolerant fuel cladding development: Promise, status, and challenges". United States. https://doi.org/10.1016/j.jnucmat.2017.12.043. https://www.osti.gov/servlets/purl/1471930.
@article{osti_1471930,
title = {Accident tolerant fuel cladding development: Promise, status, and challenges},
author = {Terrani, Kurt A.},
abstractNote = {The motivation for transitioning away from zirconium-based fuel cladding in light water reactors to significantly more oxidation-resistant materials, thereby enhancing safety margins during severe accidents, is laid out. A review of the development status for three accident tolerant fuel cladding technologies, namely coated zirconium-based cladding, ferritic alumina-forming alloy cladding, and silicon carbide fiber–reinforced silicon carbide matrix composite cladding, is offered. Technical challenges and data gaps for each of these cladding technologies are highlighted. Full development towards commercial deployment of these technologies is identified as a high priority for the nuclear industry.},
doi = {10.1016/j.jnucmat.2017.12.043},
journal = {Journal of Nuclear Materials},
number = C,
volume = 501,
place = {United States},
year = {Sat Jan 13 00:00:00 EST 2018},
month = {Sat Jan 13 00:00:00 EST 2018}
}
Web of Science
Figures / Tables:
Works referenced in this record:
Thermal Neutron Capture Cross Sections
journal, August 1951
- Pomerance, H.
- Physical Review, Vol. 83, Issue 3
Advanced oxidation-resistant iron-based alloys for LWR fuel cladding
journal, May 2014
- Terrani, K. A.; Zinkle, S. J.; Snead, L. L.
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
The Future of Low-Carbon Electricity
journal, October 2017
- Greenblatt, Jeffery B.; Brown, Nicholas R.; Slaybaugh, Rachel
- Annual Review of Environment and Resources, Vol. 42, Issue 1
Fuel R & D to Improve Fuel Reliability
journal, September 2006
- Yang, Rosa; Cheng, Bo; Deshon, Jeff
- Journal of Nuclear Science and Technology, Vol. 43, Issue 9
Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding
journal, July 2015
- Motta, Arthur T.; Couet, Adrien; Comstock, Robert J.
- Annual Review of Materials Research, Vol. 45, Issue 1
Accident tolerant fuels for LWRs: A perspective
journal, May 2014
- Zinkle, S. J.; Terrani, K. A.; Gehin, J. C.
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions
journal, May 2014
- Ott, L. J.; Robb, K. R.; Wang, D.
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
Scoping assessments of ATF impact on late-stage accident progression including molten core–concrete interaction
journal, May 2014
- Farmer, M. T.; Leibowitz, L.; Terrani, K. A.
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
Modification of MELCOR for severe accident analysis of candidate accident tolerant cladding materials
journal, April 2017
- Merrill, Brad J.; Bragg-Sitton, Shannon M.; Humrickhouse, Paul W.
- Nuclear Engineering and Design, Vol. 315
Research and Development Methodology for Practical Use of Accident Tolerant Fuel in Light Water Reactors
journal, February 2016
- Kurata, Masaki
- Nuclear Engineering and Technology, Vol. 48, Issue 1
KAERI’s Development of LWR Accident-Tolerant Fuel
journal, May 2014
- Koo, Yang-Hyun; Yang, Jae-Ho; Park, Jeong-Yong
- Nuclear Technology, Vol. 186, Issue 2
Oxidation of fuel cladding candidate materials in steam environments at high temperature and pressure
journal, August 2012
- Cheng, Ting; Keiser, James R.; Brady, Michael P.
- Journal of Nuclear Materials, Vol. 427, Issue 1-3
High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments
journal, September 2013
- Pint, B. A.; Terrani, K. A.; Brady, M. P.
- Journal of Nuclear Materials, Vol. 440, Issue 1-3
Silicon Carbide Oxidation in Steam up to 2 MPa
journal, July 2014
- Terrani, Kurt A.; Pint, Bruce A.; Parish, Chad M.
- Journal of the American Ceramic Society, Vol. 97, Issue 8
Oxidation of Advanced Zirconium Cladding Alloys in Steam at Temperatures in the Range of 600–1200 °C
journal, March 2011
- Steinbrück, Martin; Vér, Nóra; Große, Mirco
- Oxidation of Metals, Vol. 76, Issue 3-4
The Effect of Oxide Volatilization on the Oxidation Kinetics of Cr and Fe-Cr Alloys
journal, January 1966
- Tedmon, C. S.
- Journal of The Electrochemical Society, Vol. 113, Issue 8
Alumina Volatility in Water Vapor at Elevated Temperatures
journal, September 2004
- Opila, Elizabeth J.; Myers, Dwight L.
- Journal of the American Ceramic Society, Vol. 87, Issue 9
The effect of H2O gas on volatilities of planet-forming major elements: I. Experimental determination of thermodynamic properties of Ca-, Al-, and Si-hydroxide gas molecules and its application to the solar nebula
journal, January 1992
- Hashimoto, Akihiko
- Geochimica et Cosmochimica Acta, Vol. 56, Issue 1
Mechanisms of irradiation growth of alpha-zirconium alloys
journal, October 1988
- Holt, R. A.
- Journal of Nuclear Materials, Vol. 159
Irradiation-induced densification of UO2 pellet fuel
journal, November 1976
- Freshley, M. D.; Brite, D. W.; Daniel, J. L.
- Journal of Nuclear Materials, Vol. 62, Issue 2-3
Experimental Observations on Fuel Pellet Performance at High Burnup
journal, September 2006
- Serna, Juan J.; Tolonen, Pekka; Abeta, Sadaaki
- Journal of Nuclear Science and Technology, Vol. 43, Issue 9
Pellet-clad interaction (PCI) failures of zirconium alloy fuel cladding — A review
journal, August 1990
- Cox, B.
- Journal of Nuclear Materials, Vol. 172, Issue 3
Cracking of cladding tubes caused by power ramping and by laboratory stress corrosion experiments
journal, December 1979
- Videm, K.; Lunde, L.; Hollowell, T.
- Journal of Nuclear Materials, Vol. 87, Issue 2-3
The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors
journal, January 2017
- Brown, Nicholas R.; Wysocki, Aaron J.; Terrani, Kurt A.
- Annals of Nuclear Energy, Vol. 99
Radiation-Induced Creep of UO2
journal, March 1973
- Solomon, A. A.
- Journal of the American Ceramic Society, Vol. 56, Issue 3
Development of microstructure and irradiation hardening of Zircaloy during low dose neutron irradiation at nominally 358°C
journal, November 2011
- Cockeram, B. V.; Smith, R. W.; Leonard, K. J.
- Journal of Nuclear Materials, Vol. 418, Issue 1-3
Development of microstructure and irradiation hardening of Zircaloy during low dose neutron irradiation at nominally 377–440°C
journal, June 2014
- Cockeram, B. V.; Leonard, K. J.; Byun, T. S.
- Journal of Nuclear Materials, Vol. 449, Issue 1-3
Tensile properties of candidate SNS target container materials after proton and neutron irradiation in the LANSCE accelerator
journal, July 2001
- Farrell, K.; Byun, T. S.
- Journal of Nuclear Materials, Vol. 296, Issue 1-3
Investigation of Hydride Rim Effect on Failure of Zircaloy-4 Cladding with Tube Burst Test
journal, January 2005
- Nagase, Fumihisa; Fuketa, Toyoshi
- Journal of Nuclear Science and Technology, Vol. 42, Issue 1
Materials challenges in nuclear energy
journal, February 2013
- Zinkle, S. J.; Was, G. S.
- Acta Materialia, Vol. 61, Issue 3
Fuels for sodium-cooled fast reactors: US perspective
journal, September 2007
- Crawford, Douglas C.; Porter, Douglas L.; Hayes, Steven L.
- Journal of Nuclear Materials, Vol. 371, Issue 1-3
Hydrogen pickup measurements in zirconium alloys: Relation to oxidation kinetics
journal, August 2014
- Couet, Adrien; Motta, Arthur T.; Comstock, Robert J.
- Journal of Nuclear Materials, Vol. 451, Issue 1-3
The effect of fuel thermal conductivity on the behavior of LWR cores during loss-of-coolant accidents
journal, May 2014
- Terrani, Kurt A.; Wang, Dean; Ott, Larry J.
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
Failure of high burnup fuels under reactivity-initiated accident conditions
journal, April 2009
- Sugiyama, Tomoyuki; Umeda, Miki; Fuketa, Toyoshi
- Annals of Nuclear Energy, Vol. 36, Issue 3
Comparative Analysis of Station Blackout Accident Progression in Typical pwr, bwr, and phwr
journal, April 2012
- Park, Soo-Yong; Ahn, Kwang-Il
- Nuclear Engineering and Technology, Vol. 44, Issue 3
Current knowledge on core degradation phenomena, a review
journal, April 1999
- Hofmann, P.
- Journal of Nuclear Materials, Vol. 270, Issue 1-2
Protective coatings on zirconium-based alloys as accident-tolerant fuel (ATF) claddings
journal, August 2017
- Tang, Chongchong; Stueber, Michael; Seifert, Hans Juergen
- Corrosion Reviews, Vol. 35, Issue 3
Mechanical analysis of surface-coated zircaloy cladding
journal, August 2017
- Lee, Youho; Lee, Jeong Ik; No, Hee Cheon
- Nuclear Engineering and Technology, Vol. 49, Issue 5
Neutronic evaluation of coating and cladding materials for accident tolerant fuels
journal, April 2016
- Younker, Ian; Fratoni, Massimiliano
- Progress in Nuclear Energy, Vol. 88
Critical heat flux for SiC- and Cr-coated plates under atmospheric condition
journal, February 2015
- Kam, Dong Hoon; Lee, Jong Hyuk; Lee, Taeseung
- Annals of Nuclear Energy, Vol. 76
Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating
journal, October 2015
- Kim, Hyun-Gil; Kim, Il-Hyun; Jung, Yang-Il
- Journal of Nuclear Materials, Vol. 465
Investigation of the impact of coatings on corrosion and hydrogen uptake of Zircaloy-4
journal, December 2015
- Daub, K.; Van Nieuwenhove, R.; Nordin, H.
- Journal of Nuclear Materials, Vol. 467
Vacuum-arc chromium-based coatings for protection of zirconium alloys from the high-temperature oxidation in air
journal, October 2015
- Kuprin, А. S.; Belous, V. А.; Voyevodin, V. N.
- Journal of Nuclear Materials, Vol. 465
High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings
journal, October 2015
- Park, Jung-Hwan; Kim, Hyun-Gil; Park, Jeong-yong
- Surface and Coatings Technology, Vol. 280
Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions
journal, December 2016
- Park, Dong Jun; Kim, Hyun Gil; Jung, Yang Il
- Journal of Nuclear Materials, Vol. 482
Designing Radiation Resistance in Materials for Fusion Energy
journal, July 2014
- Zinkle, S. J.; Snead, L. L.
- Annual Review of Materials Research, Vol. 44, Issue 1
Prototypical experiments relating to air oxidation of Zircaloy-4 at high temperatures
journal, August 2009
- Steinbrück, Martin
- Journal of Nuclear Materials, Vol. 392, Issue 3
The MN+1AXN phases: A new class of solids: Thermodynamically stable nanolaminates
journal, January 2000
- Barsoum, Michel W.
- Progress in Solid State Chemistry, Vol. 28, Issue 1-4, p. 201-281
Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding
journal, November 2015
- Maier, Benjamin R.; Garcia-Diaz, Brenda L.; Hauch, Benjamin
- Journal of Nuclear Materials, Vol. 466
Laser surface annealing and characterization of Ti2AlC plasma vapor deposition coating on zirconium-alloy substrate
journal, September 2016
- Yeom, Hwasung; Hauch, Benjamin; Cao, Guoping
- Thin Solid Films, Vol. 615
Ceramic coating for corrosion (c3) resistance of nuclear fuel cladding
journal, November 2015
- Alat, Ece; Motta, Arthur T.; Comstock, Robert J.
- Surface and Coatings Technology, Vol. 281
Multilayer (TiN, TiAlN) ceramic coatings for nuclear fuel cladding
journal, September 2016
- Alat, Ece; Motta, Arthur T.; Comstock, Robert J.
- Journal of Nuclear Materials, Vol. 478
Protection of zirconium by alumina- and chromia-forming iron alloys under high-temperature steam exposure
journal, July 2013
- Terrani, Kurt A.; Parish, Chad M.; Shin, Dongwon
- Journal of Nuclear Materials, Vol. 438, Issue 1-3
Anisotropic swelling and microcracking of neutron irradiated Ti3AlC2–Ti5Al2C3 materials
journal, March 2016
- Ang, Caen; Silva, Chinthaka; Shih, Chunghao
- Scripta Materialia, Vol. 114
Phase stability, swelling, microstructure and strength of Ti3SiC2-TiC ceramics after low dose neutron irradiation
journal, January 2017
- Ang, Caen; Zinkle, Steven; Shih, Chunghao
- Journal of Nuclear Materials, Vol. 483
Undoped and ytterbium-doped titanium aluminum nitride coatings for improved oxidation behavior of nuclear fuel cladding
journal, December 2017
- Brova, Michael J.; Alat, Ece; Pauley, Mark A.
- Surface and Coatings Technology, Vol. 331
Performance of Metallic Fuels and Blankets in Liquid-Metal Fast Breeder Reactors
journal, May 1984
- Walters, Leon C.; Seidel, B. R.; Kittel, J. Howard
- Nuclear Technology, Vol. 65, Issue 2
Steam Oxidation Evaluation of Fe–Cr Alloys for Accident Tolerant Nuclear Fuel Cladding
journal, March 2017
- Pint, B. A.; Unocic, K. A.
- Oxidation of Metals, Vol. 87, Issue 3-4
The 885° f (475° c) embrittlement of ferritic stainless steels
journal, January 1973
- Grobner, P. J.
- Metallurgical Transactions, Vol. 4, Issue 1
α′ precipitation in neutron-irradiated Fe–Cr alloys
journal, March 2014
- Bachhav, Mukesh; Robert Odette, G.; Marquis, Emmanuelle A.
- Scripta Materialia, Vol. 74
Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors
journal, January 2015
- George, Nathan Michael; Terrani, Kurt; Powers, Jeff
- Annals of Nuclear Energy, Vol. 75
The development of alumina-forming austenitic stainless steels for high-temperature structural use
journal, July 2008
- Brady, M. P.; Yamamoto, Y.; Santella, M. L.
- JOM, Vol. 60, Issue 7
Effect of steam on high temperature oxidation behaviour of alumina-forming alloys
journal, January 2015
- Pint, B. A.; Unocic, K. A.; Terrani, K. A.
- Materials at High Temperatures, Vol. 32, Issue 1-2
Performance of FeCrAl for accident-tolerant fuel cladding in high-temperature steam
journal, August 2017
- Pint, Bruce A.
- Corrosion Reviews, Vol. 35, Issue 3
Effect of Al and Cr Content on Air and Steam Oxidation of FeCrAl Alloys and Commercial APMT Alloy
journal, March 2017
- Unocic, Kinga A.; Yamamoto, Yukinori; Pint, Bruce A.
- Oxidation of Metals, Vol. 87, Issue 3-4
Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors
journal, December 2015
- Yamamoto, Y.; Pint, B. A.; Terrani, K. A.
- Journal of Nuclear Materials, Vol. 467
Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys
journal, October 2015
- Field, Kevin G.; Hu, Xunxiang; Littrell, Kenneth C.
- Journal of Nuclear Materials, Vol. 465
Irradiation-enhanced α′ precipitation in model FeCrAl alloys
journal, April 2016
- Edmondson, P. D.; Briggs, S. A.
- Scripta Materialia, Vol. 116
A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys
journal, May 2017
- Briggs, Samuel A.; Edmondson, Philip D.; Littrell, Kenneth C.
- Acta Materialia, Vol. 129
Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys
journal, June 2017
- Field, Kevin G.; Briggs, Samuel A.; Sridharan, Kumar
- Journal of Nuclear Materials, Vol. 489
Microstructure and environmental resistance of low Cr ODS FeCrAl
journal, January 2015
- Unocic, K. A.; Hoelzer, D. T.; Pint, B. A.
- Materials at High Temperatures, Vol. 32, Issue 1-2
Performance degradation of candidate accident-tolerant cladding under corrosive environment
journal, August 2017
- Nagase, Fumihisa; Sakamoto, Kan; Yamashita, Shinichiro
- Corrosion Reviews, Vol. 35, Issue 3
Design, properties, and weldability of advanced oxidation-resistant FeCrAl alloys
journal, September 2017
- Gussev, M. N.; Field, K. G.; Yamamoto, Y.
- Materials & Design, Vol. 129
Solid-liquid phase equilibria of Fe-Cr-Al alloys and spinels
journal, August 2017
- McMurray, J. W.; Hu, R.; Ushakov, S. V.
- Journal of Nuclear Materials, Vol. 492
Microstructural control of FeCrAl alloys using Mo and Nb additions
journal, October 2017
- Sun, Zhiqian; Bei, Hongbin; Yamamoto, Yukinori
- Materials Characterization, Vol. 132
Processability evaluation of a Mo-containing FeCrAl alloy for seamless thin-wall tube fabrication
journal, July 2017
- Sun, Zhiqian; Yamamoto, Yukinori
- Materials Science and Engineering: A, Vol. 700
Development of ODS FeCrAl for Compatibility in Fusion and Fission Energy Applications
journal, November 2014
- Pint, B. A.; Dryepondt, S.; Unocic, K. A.
- JOM, Vol. 66, Issue 12
Ultra-high temperature tensile properties of ODS steel claddings under severe accident conditions
journal, April 2017
- Yano, Y.; Tanno, T.; Oka, H.
- Journal of Nuclear Materials, Vol. 487
Deformation behavior of laser welds in high temperature oxidation resistant Fe–Cr–Al alloys for fuel cladding applications
journal, November 2014
- Field, Kevin G.; Gussev, Maxim N.; Yamamoto, Yukinori
- Journal of Nuclear Materials, Vol. 454, Issue 1-3
Uniform corrosion of FeCrAl alloys in LWR coolant environments
journal, October 2016
- Terrani, K. A.; Pint, B. A.; Kim, Y. -J.
- Journal of Nuclear Materials, Vol. 479
Characterization of oxides formed on iron-chromium-aluminum alloy in simulated light water reactor environments
journal, August 2017
- Rebak, Raul B.; Larsen, Michael; Kim, Young-Jin
- Corrosion Reviews, Vol. 35, Issue 3
A proposed method of calculating displacement dose rates
journal, August 1975
- Norgett, M. J.; Robinson, M. T.; Torrens, I. M.
- Nuclear Engineering and Design, Vol. 33, Issue 1
An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions
journal, August 2017
- Gamble, K. A.; Barani, T.; Pizzocri, D.
- Journal of Nuclear Materials, Vol. 491
Fuel performance simulation of iron-chrome-aluminum (FeCrAl) cladding during steady-state LWR operation
journal, March 2018
- Sweet, R. T.; George, N. M.; Maldonado, G. I.
- Nuclear Engineering and Design, Vol. 328
Potential impact of accident tolerant fuel cladding critical heat flux characteristics on the high temperature phase of reactivity initiated accidents
journal, December 2017
- Liu, Maolong; Brown, Nicholas R.; Terrani, Kurt A.
- Annals of Nuclear Energy, Vol. 110
Cladding burst behavior of Fe-based alloys under LOCA
journal, March 2016
- Massey, Caleb P.; Terrani, Kurt A.; Dryepondt, Sebastien N.
- Journal of Nuclear Materials, Vol. 470
Post-quench ductility evaluation of Zircaloy-4 and select iron alloys under design basis and extended LOCA conditions
journal, May 2014
- Yan, Y.; Keiser, J. R.; Terrani, K. A.
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
Advanced TEM characterization of oxide nanoparticles in ODS Fe–12Cr–5Al alloys
journal, July 2016
- Unocic, Kinga A.; Pint, Bruce A.; Hoelzer, David T.
- Journal of Materials Science, Vol. 51, Issue 20
A pulse-controlled modified-burst test instrument for accident-tolerant fuel cladding
journal, November 2017
- Cinbiz, M. Nedim; Brown, Nicholas R.; Terrani, Kurt A.
- Annals of Nuclear Energy, Vol. 109
Experimental observations in support of the dynamic-segregation theory to explain the reactive-element effect
journal, February 1996
- Pint, B. A.
- Oxidation of Metals, Vol. 45, Issue 1-2
Neutron cross section sensitivity and uncertainty analysis of candidate accident tolerant fuel concepts
journal, December 2017
- Burns, Joseph R.; Brown, Nicholas R.
- Annals of Nuclear Energy, Vol. 110
Screening of advanced cladding materials and UN–U3Si5 fuel
journal, July 2015
- Brown, Nicholas R.; Todosow, Michael; Cuadra, Arantxa
- Journal of Nuclear Materials, Vol. 462
Influence of the Cr content on the permeation of hydrogen in Fe alloys
journal, November 2013
- Peñalva, I.; Alberro, G.; Aranburu, J.
- Journal of Nuclear Materials, Vol. 442, Issue 1-3
Hydrogen permeation in FeCrAl alloys for LWR cladding application
journal, June 2015
- Hu, Xunxiang; Terrani, Kurt A.; Wirth, Brian D.
- Journal of Nuclear Materials, Vol. 461
Thermodynamics of the Zr-H System
journal, December 1995
- Wang, Wei-E; Olander, Donald R.
- Journal of the American Ceramic Society, Vol. 78, Issue 12
Hydrogen Permeation Through Metals, Alloys and Oxides at Elevated Temperatures
journal, September 1960
- Huffine, C. L.; Williams, J. M.
- CORROSION, Vol. 16, Issue 9
Synopsis and outcome of the QUENCH experimental program
journal, July 2010
- Steinbrück, M.; Große, M.; Sepold, L.
- Nuclear Engineering and Design, Vol. 240, Issue 7
Development of a silicon carbide fibre with high tensile strength
journal, June 1976
- Yajima, S.; Hayashi, J.; Omori, M.
- Nature, Vol. 261, Issue 5562
Synthesis of Continuous Sic Fibers with High Tensile Strength
journal, July 1976
- Yajima, Seishi; Okamura, Kiyohito; Hayashi, Josaburo
- Journal of the American Ceramic Society, Vol. 59, Issue 7-8
Effects of fast-neutron irradiation on pyrolytic silicon carbide
journal, October 1969
- Price, R. J.
- Journal of Nuclear Materials, Vol. 33, Issue 1
Continuous SiC fiber, CVI SiC matrix composites for nuclear applications: Properties and irradiation effects
journal, May 2014
- Katoh, Yutai; Ozawa, Kazumi; Shih, Chunghao
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
Irradiation-induced shrinkage of highly crystalline SiC fibers
journal, January 2015
- Kondo, Sosuke; Hinoki, Tatsuya; Nonaka, Makoto
- Acta Materialia, Vol. 83
SiC/SiC composites through transient eutectic-phase route for fusion applications
journal, August 2004
- Katoh, Y.; Kohyama, A.; Nozawa, T.
- Journal of Nuclear Materials, Vol. 329-333, p. 587-591
Design, preparation and properties of non-oxide CMCs for application in engines and nuclear reactors: an overview
journal, February 2004
- Naslain, R.
- Composites Science and Technology, Vol. 64, Issue 2
Thermo-mechanical properties and microstructure of silicon carbide composites fabricated by nano-infiltrated transient eutectoid process
journal, November 2002
- Katoh, Y.; Dong, S. M.; Kohyama, A.
- Fusion Engineering and Design, Vol. 61-62
Melt Infiltration Approach to Ceramic Matrix Composites
journal, February 1988
- Hillig, William B.
- Journal of the American Ceramic Society, Vol. 71, Issue 2
Development of high-strength reaction-sintered silicon carbide
journal, March 2003
- Suyama, S.; Kameda, T.; Itoh, Y.
- Diamond and Related Materials, Vol. 12, Issue 3-7
High-performance SiC/SiC composites by improved PIP processing with new precursor polymers
journal, December 2000
- Kohyama, A.; Kotani, M.; Katoh, Y.
- Journal of Nuclear Materials, Vol. 283-287
Handbook of SiC properties for fuel performance modeling
journal, September 2007
- Snead, Lance L.; Nozawa, Takashi; Katoh, Yutai
- Journal of Nuclear Materials, Vol. 371, Issue 1-3
Paralinear Oxidation of CVD SiC in Water Vapor
journal, January 1997
- Opila, Elizabeth J.; Hann, Raiford E.
- Journal of the American Ceramic Society, Vol. 80, Issue 1
High-temperature tensile strength of near-stoichiometric SiC/SiC composites
journal, December 2002
- Hironaka, K.; Nozawa, T.; Hinoki, T.
- Journal of Nuclear Materials, Vol. 307-311
Enchanced high-temperature performances of SiC/SiC composites by high densification and crystalline structure
journal, February 2011
- Shimoda, Kazuya; Hinoki, Tatsuya; Kishimoto, Hirotatsu
- Composites Science and Technology, Vol. 71, Issue 3, p. 326-332
Development of Silicon Carbide Composites for Fusion
journal, August 1993
- Lance, L. Snead
- Fusion Technology, Vol. 24, Issue 1
Current status and critical issues for development of SiC composites for fusion applications
journal, August 2007
- Katoh, Y.; Snead, L. L.; Henager, C. H.
- Journal of Nuclear Materials, Vol. 367-370
Radiation effects in SiC for nuclear structural applications
journal, June 2012
- Katoh, Yutai; Snead, Lance L.; Szlufarska, Izabela
- Current Opinion in Solid State and Materials Science, Vol. 16, Issue 3
Characterization of SiC–SiC composites for accident tolerant fuel cladding
journal, November 2015
- Deck, C. P.; Jacobsen, G. M.; Sheeder, J.
- Journal of Nuclear Materials, Vol. 466
Fabrication and measurement of hoop strength of SiC triplex tube for nuclear fuel cladding applications
journal, March 2015
- Kim, Daejong; Lee, Hyun-Geun; Park, Ji Yeon
- Journal of Nuclear Materials, Vol. 458
Stability of SiC and its composites at high neutron fluence
journal, October 2011
- Katoh, Yutai; Nozawa, Takashi; Snead, Lance L.
- Journal of Nuclear Materials, Vol. 417, Issue 1-3
Vapor-Phase Fabrication and Properties of Continuous-Filament Ceramic Composites
journal, September 1991
- Besmann, T. M.; Sheldon, B. W.; Lowden, R. A.
- Science, Vol. 253, Issue 5024
Fabrication of tubular SiCf/SiC using different preform architectures by electrophoretic deposition and hot pressing
journal, July 2017
- Fitriani, Pipit; Sharma, Amit Siddharth; Septiadi, Arifin
- Ceramics International, Vol. 43, Issue 10
Preparation of SiC/SiC Composites by Hot Pressing, Using Tyranno-SA Fiber as Reinforcement
journal, January 2003
- Dong, Shaoming; Katoh, Yutai; Kohyama, Akira
- Journal of the American Ceramic Society, Vol. 86, Issue 1
Development of the tailored SiC/SiC composites by the combined fabrication process of ICVI and NITE methods
journal, February 2009
- Shimoda, Kazuya; Hinoki, Tatsuya; Katoh, Yutai
- Journal of Nuclear Materials, Vol. 384, Issue 2, p. 103-108
Mechanical properties of SiC/SiC braided tubes for fuel cladding
journal, October 2014
- Rohmer, Eric; Martin, Eric; Lorrette, Christophe
- Journal of Nuclear Materials, Vol. 453, Issue 1-3
Investigation of the C-ring test for measuring hoop tensile strength of nuclear grade ceramic composites
journal, September 2014
- Jacobsen, G. M.; Stone, J. D.; Khalifa, H. E.
- Journal of Nuclear Materials, Vol. 452, Issue 1-3
Radiation-tolerant joining technologies for silicon carbide ceramics and composites
journal, May 2014
- Katoh, Yutai; Snead, Lance L.; Cheng, Ting
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
Thermophysical and mechanical properties of near-stoichiometric fiber CVI SiC/SiC composites after neutron irradiation at elevated temperatures
journal, August 2010
- Katoh, Yutai; Snead, Lance L.; Nozawa, Takashi
- Journal of Nuclear Materials, Vol. 403, Issue 1-3
Effects of neutron irradiation on mechanical properties of silicon carbide composites fabricated by nano-infiltration and transient eutectic-phase process
journal, May 2014
- Koyanagi, Takaaki; Ozawa, Kazumi; Hinoki, Tatsuya
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
Strength of SiCf-SiCm composite tube under uniaxial and multiaxial loading
journal, March 2018
- Shapovalov, Kirill; Jacobsen, George M.; Alva, Luis
- Journal of Nuclear Materials, Vol. 500
Fabrication and characterization of joined silicon carbide cylindrical components for nuclear applications
journal, February 2015
- Khalifa, H. E.; Deck, C. P.; Gutierrez, O.
- Journal of Nuclear Materials, Vol. 457
Irradiation resistance of silicon carbide joint at light water reactor–relevant temperature
journal, May 2017
- Koyanagi, T.; Katoh, Y.; Kiggans, J. O.
- Journal of Nuclear Materials, Vol. 488
High-dose neutron irradiation of Hi-Nicalon Type S silicon carbide composites. Part 2: Mechanical and physical properties
journal, July 2015
- Katoh, Yutai; Nozawa, Takashi; Shih, Chunghao
- Journal of Nuclear Materials, Vol. 462
Mechanical properties of SiC composites neutron irradiated under light water reactor relevant temperature and dose conditions
journal, October 2017
- Koyanagi, Takaaki; Katoh, Yutai
- Journal of Nuclear Materials, Vol. 494
Chemical reactivity of CVC and CVD SiC with UO2 at high temperatures
journal, May 2015
- Silva, Chinthaka M.; Katoh, Yutai; Voit, Stewart L.
- Journal of Nuclear Materials, Vol. 460
Chemical compatibility between UO 2 fuel and SiC cladding for LWRs. Application to ATF (Accident-Tolerant Fuels)
journal, April 2017
- Braun, James; Guéneau, Christine; Alpettaz, Thierry
- Journal of Nuclear Materials, Vol. 487
Safety Assessment of SiC Cladding Oxidation under Loss-of-Coolant Accident Conditions in Light Water Reactors
journal, August 2013
- Lee, Youho; McKrell, Thomas J.; Yue, Chao
- Nuclear Technology, Vol. 183, Issue 2
Oxidation at high temperatures in steam atmosphere and quench of silicon carbide composites for nuclear application
journal, December 2015
- Angelici Avincola, V.; Grosse, M.; Stegmaier, U.
- Nuclear Engineering and Design, Vol. 295
Silicon carbide composite for light water reactor fuel assembly applications
journal, May 2014
- Yueh, Ken; Terrani, Kurt A.
- Journal of Nuclear Materials, Vol. 448, Issue 1-3
FABRICATION AND MATERIAL ISSUES FOR THE APPLICATION OF SiC COMPOSITES TO LWR FUEL CLADDING
journal, August 2013
- Kim, Weon-Ju; Kim, Daejong; Park, Ji Yeon
- Nuclear Engineering and Technology, Vol. 45, Issue 4
Corrosion Behavior of Silicon Carbide in 290oC Water
journal, November 1989
- Hirayama, Hideo; Kawakubo, Takashi; Goto, Akira
- Journal of the American Ceramic Society, Vol. 72, Issue 11
Pitting corrosion in CVD SiC at 300°C in deoxygenated high-purity water
journal, August 2008
- Henager, Charles H.; Schemer-Kohrn, Alan L.; Pitman, Stan G.
- Journal of Nuclear Materials, Vol. 378, Issue 1
Thermodynamic and experimental study of carbon formation on carbides under hydrothermal conditions
journal, January 1995
- Jacobson, Nathan S.; Gogotsi, Yury G.; Yoshimura, Masahiro
- Journal of Materials Chemistry, Vol. 5, Issue 4
Hydrothermal corrosion of SiC in LWR coolant environments in the absence of irradiation
journal, October 2015
- Terrani, K. A.; Yang, Y.; Kim, Y. -J.
- Journal of Nuclear Materials, Vol. 465
Correlating quartz dissolution kinetics in pure water from 25 to 625°C
journal, June 1994
- Tester, Jefferson W.; Worley, W. Gabriel; Robinson, Bruce A.
- Geochimica et Cosmochimica Acta, Vol. 58, Issue 11
The dissolution kinetics of amorphous silica into sodium chloride solutions: effects of temperature and ionic strength
journal, December 2000
- Icenhower, Jonathan P.; Dove, Patricia M.
- Geochimica et Cosmochimica Acta, Vol. 64, Issue 24
Effect of dissolved hydrogen on the corrosion behavior of chemically vapor deposited SiC in a simulated pressurized water reactor environment
journal, September 2015
- Kim, Daejong; Lee, Hyeon-Geun; Park, Ji Yeon
- Corrosion Science, Vol. 98
Hydrothermal corrosion of silicon carbide joints without radiation
journal, December 2016
- Koyanagi, Takaaki; Katoh, Yutai; Terrani, Kurt A.
- Journal of Nuclear Materials, Vol. 481
Microstructure and hydrothermal corrosion behavior of NITE-SiC with various sintering additives in LWR coolant environments
journal, April 2017
- Parish, Chad M.; Terrani, Kurt A.; Kim, Young-Jin
- Journal of the European Ceramic Society, Vol. 37, Issue 4
Effect of irradiation damage on hydrothermal corrosion of SiC
journal, September 2015
- Kondo, Sosuke; Lee, Moonhee; Hinoki, Tatsuya
- Journal of Nuclear Materials, Vol. 464
Viability of Hydrogen Water Chemistry for Protecting In-Vessel Components of Boiling Water Reactors
journal, March 1992
- Macdonald, D. D.
- CORROSION, Vol. 48, Issue 3
Role of irradiation-induced defects on SiC dissolution in hot water
journal, November 2016
- Kondo, Sosuke; Mouri, Shinichiro; Hyodo, Yoshihiro
- Corrosion Science, Vol. 112
Long-term corrosion behavior of CVD SiC in 360°C water and 400°C steam
journal, November 2013
- Park, Jeong-Yong; Kim, Il-Hyun; Jung, Yang-Il
- Journal of Nuclear Materials, Vol. 443, Issue 1-3
Characteristics of Composite Silicon Carbide Fuel Cladding after Irradiation under Simulated PWR Conditions
journal, July 2013
- Stempien, John D.; Carpenter, David M.; Kohse, Gordon
- Nuclear Technology, Vol. 183, Issue 1
Re-defining failure envelopes for silicon carbide composites based on damage process analysis by acoustic emission
journal, October 2013
- Nozawa, Takashi; Ozawa, Kazumi; Tanigawa, Hiroyasu
- Fusion Engineering and Design, Vol. 88, Issue 9-10
Thermo-mechanical analysis of LWR SiC/SiC composite cladding
journal, April 2014
- Ben-Belgacem, M.; Richet, V.; Terrani, K. A.
- Journal of Nuclear Materials, Vol. 447, Issue 1-3
A structural model for multi-layered ceramic cylinders and its application to silicon carbide cladding of light water reactor fuel
journal, March 2015
- Lee, Youho; Kazimi, Mujid S.
- Journal of Nuclear Materials, Vol. 458
Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding
journal, November 2015
- Stone, J. G.; Schleicher, R.; Deck, C. P.
- Journal of Nuclear Materials, Vol. 466
Mechanical performance of SiC three-layer cladding in PWRs
journal, December 2016
- Angelici Avincola, Valentina; Guenoun, Pierre; Shirvan, Koroush
- Nuclear Engineering and Design, Vol. 310
Thermo-mechanical assessment of full SiC/SiC composite cladding for LWR applications with sensitivity analysis
journal, February 2018
- Singh, Gyanender; Terrani, Kurt; Katoh, Yutai
- Journal of Nuclear Materials, Vol. 499
Recent research and development for the dual-coolant blanket concept in the US
journal, December 2008
- Morley, N. B.; Katoh, Y.; Malang, S.
- Fusion Engineering and Design, Vol. 83, Issue 7-9
Parametric Evaluation of SiC/SiC Composite Cladding with UO2 Fuel for LWR Applications: Fuel Rod Interactions and Impact of Nonuniform Power Profile in Fuel Rod
journal, February 2018
- Singh, G.; Sweet, R.; Brown, N. R.
- Journal of Nuclear Materials, Vol. 499
Experimental design and analysis for irradiation of SiC/SiC composite tubes under a prototypic high heat flux
journal, August 2017
- Petrie, Christian M.; Koyanagi, Takaaki; McDuffee, Joel L.
- Journal of Nuclear Materials, Vol. 491
Evaluating the irradiation effects on the elastic properties of miniature monolithic SiC tubular specimens
journal, February 2018
- Singh, G.; Koyanagi, T.; Petrie, C.
- Journal of Nuclear Materials, Vol. 499
SiC Recession Caused by SiO 2 Scale Volatility under Combustion Conditions: II, Thermodynamics and Gaseous-Diffusion Model
journal, July 1999
- Opila, Elizabeth J.; Smialek, James L.; Robinson, Raymond C.
- Journal of the American Ceramic Society, Vol. 82, Issue 7
Oxidation and Volatilization of Silica Formers in Water Vapor
journal, August 2003
- Opila, Elizabeth J.
- Journal of the American Ceramic Society, Vol. 86, Issue 8
Observations of Accelerated Silicon Carbide Recession by Oxidation at High Water-Vapor Pressures
journal, January 2000
- More, Karren L.; Tortorelli, Peter F.; Ferber, Mattison K.
- Journal of the American Ceramic Society, Vol. 83, Issue 1
High-Temperature Stability of SiC-Based Composites in High-Water-Vapor-Pressure Environments
journal, August 2003
- More, Karren L.; Tortorelli, Peter F.; Walker, Larry R.
- Journal of the American Ceramic Society, Vol. 86, Issue 8
Steam oxidation of fuel in defective LWR rods
journal, April 1999
- Olander, D. R.; Soo Kim, Yeon; Wang, Wei-E
- Journal of Nuclear Materials, Vol. 270, Issue 1-2
A conceptual model for the fuel oxidation of defective fuel
journal, June 2007
- Higgs, J. D.; Lewis, B. J.; Thompson, W. T.
- Journal of Nuclear Materials, Vol. 366, Issue 1-2
Materials chemistry and transport modeling for severe accident analyses in light-water reactors III. Fuel dissolution by molten cladding
journal, April 1996
- Olander, D. R.
- Nuclear Engineering and Design, Vol. 162, Issue 2-3
Oxidation behavior of U-Si compounds in air from 25 to 1000 C
journal, February 2017
- Sooby Wood, E.; White, J. T.; Nelson, A. T.
- Journal of Nuclear Materials, Vol. 484
Degradation of UN and UN–U 3 Si 2 pellets in steam environment
journal, January 2017
- Lopes, Denise Adorno; Uygur, Selim; Johnson, Kyle
- Journal of Nuclear Science and Technology, Vol. 54, Issue 4
Motivation for utilizing new high-performance advanced materials in nuclear energy systems
journal, December 2016
- Zinkle, S. J.; Terrani, K. A.; Snead, L. L.
- Current Opinion in Solid State and Materials Science, Vol. 20, Issue 6
An approach to fuel development and qualification
journal, September 2007
- Crawford, Douglas C.; Porter, Douglas L.; Hayes, Steven L.
- Journal of Nuclear Materials, Vol. 371, Issue 1-3
Reactor Safety Gap Evaluation of Accident-Tolerant Components and Severe Accident Analysis
journal, November 2016
- Farmer, M. T.; Bunt, R.; Corradini, M.
- Nuclear Science and Engineering, Vol. 184, Issue 3
Works referencing / citing this record:
Hydrogen Interaction with Deep Surface Modified Zr-1Nb Alloy by High Intensity Ti Ion Implantation
journal, December 2018
- Kashkarov, Egor; Ryabchikov, Alexander; Kurochkin, Alexander
- Metals, Vol. 8, Issue 12
Oxidation Characteristics of Two FeCrAl Alloys in Air and Steam from 800°C to 1300°C
journal, June 2018
- Rebak, Raul B.; Gupta, Vipul K.; Larsen, Michael
- JOM, Vol. 70, Issue 8
Effectiveness of Cr-Coated Zr-Alloy Clad in Delaying Fuel Degradation for a PWR During a Station Blackout Event
journal, August 2019
- Wang, J.; Yeom, H.; Humrickhouse, P.
- Nuclear Technology, Vol. 206, Issue 3
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